SUMMARY OF EXPERIMENTAL RESULTS FOR CERAMIC BREEDER MATERIALS

Lithium-containing ceramics were quickly recognized as promising triti um breeding materials for fusion reactor blankets, particularly becaus e of their safety advantages. Relevant material properties were invest igated to evaluate further their suitability. An extensive R&D program complemented a conceptual blanket design activity either for near-ter m machines or for power reactors. All aspects were addressed: fabricab ility; overall properties (baseline, thermal, mechanical); compatibili ty with structures and beryllium; tritium release characteristics; irr adiation behavior; activation; reprocessing; waste disposal issues. As a result of this investigation, lithium-containing ceramics are consi dered to be excellent tritium breeding materials.